Event Notification Report for May 10, 2013
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
05/09/2013 - 05/10/2013
EVENT NUMBERS
490204902149022490234902449305
Power Reactor
Event Number: 49020
Facility: NORTH ANNA
Region: 2 State: VA
Unit: [] [2] []
RX Type: [1] W-3-LP,[2] W-3-LP,[3] M-4-LP
NRC Notified By: PAGE KEMP
HQ OPS Officer: MARK ABRAMOVITZ
Region: 2 State: VA
Unit: [] [2] []
RX Type: [1] W-3-LP,[2] W-3-LP,[3] M-4-LP
NRC Notified By: PAGE KEMP
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 05/10/2013
Notification Time: 08:20 [ET]
Event Date: 05/10/2013
Event Time: 06:12 [EDT]
Last Update Date: 05/10/2013
Notification Time: 08:20 [ET]
Event Date: 05/10/2013
Event Time: 06:12 [EDT]
Last Update Date: 05/10/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
DAVID AYRES (R2DO)
DAVID AYRES (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | M/R | Y | 60 | Power Operation | 0 | Hot Standby |
MANUAL REACTOR TRIP DUE TO HIGH TURBINE BEARING VIBRATION
"On May 10, 2013 at 0612 hours [EDT], Unit 2 was manually tripped from 60% power due to increased vibrations and a report of arcing on bearing #9 of the main turbine. Unit 2 was in the process of increasing power following a refueling outage when this event occurred. The Operations crew entered the reactor trip procedure and stabilized Unit 2 in Mode 3 at normal operating temperature and pressure. All control rods fully inserted into the core following the reactor trip. This reactor protection system actuation is reportable per 10CFR50.72(b)(2)(iv)(B). The Auxiliary Feedwater pumps actuated as designed as a result of the reactor trip and provided makeup flow to the steam generators. The automatic start of the Auxiliary Feedwater system is reportable per 10CFR50.72(b)(3)(iv)(A) for a valid actuation of an ESF system. The Auxiliary Feedwater pumps were subsequently secured and returned to automatic. Decay heat is being removed by the condenser steam dump system. Unit 2 is in a normal shutdown electrical lineup."
The #9 bearing is on the main generator exciter. There was no effect on Unit 1.
The licensee notified the NRC Resident Inspector and will be notifying local government agencies.
"On May 10, 2013 at 0612 hours [EDT], Unit 2 was manually tripped from 60% power due to increased vibrations and a report of arcing on bearing #9 of the main turbine. Unit 2 was in the process of increasing power following a refueling outage when this event occurred. The Operations crew entered the reactor trip procedure and stabilized Unit 2 in Mode 3 at normal operating temperature and pressure. All control rods fully inserted into the core following the reactor trip. This reactor protection system actuation is reportable per 10CFR50.72(b)(2)(iv)(B). The Auxiliary Feedwater pumps actuated as designed as a result of the reactor trip and provided makeup flow to the steam generators. The automatic start of the Auxiliary Feedwater system is reportable per 10CFR50.72(b)(3)(iv)(A) for a valid actuation of an ESF system. The Auxiliary Feedwater pumps were subsequently secured and returned to automatic. Decay heat is being removed by the condenser steam dump system. Unit 2 is in a normal shutdown electrical lineup."
The #9 bearing is on the main generator exciter. There was no effect on Unit 1.
The licensee notified the NRC Resident Inspector and will be notifying local government agencies.
Power Reactor
Event Number: 49021
Facility: TURKEY POINT
Region: 2 State: FL
Unit: [3] [] []
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: PAUL REIMERS
HQ OPS Officer: JOHN SHOEMAKER
Region: 2 State: FL
Unit: [3] [] []
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: PAUL REIMERS
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 05/10/2013
Notification Time: 12:42 [ET]
Event Date: 05/10/2013
Event Time: 11:08 [EDT]
Last Update Date: 05/10/2013
Notification Time: 12:42 [ET]
Event Date: 05/10/2013
Event Time: 11:08 [EDT]
Last Update Date: 05/10/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
Person (Organization):
DAVID AYRES (R2DO)
DAVID AYRES (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 3 | M/R | Y | 25 | Power Operation | 0 | Hot Standby |
UNIT 3 MANUAL REACTOR TRIP DUE TO MALFUNCTION OF TURBINE VALVES
"This is a non-emergency event notification to the NRCOC [Nuclear Regulatory Commission Operations Center] in accordance with 10 CFR 50.72(b)(2)(iv)(B) for a valid actuation of the Reactor Protection System (RPS) (four hour notification).
"On 5/10/13 [at 1108 EDT] Unit 3 was stabilizing at 25% [power] during a controlled shutdown from an initial power level of 38% [power]. Prior to the planned insertion of the trip at 25% [power], a malfunction of the turbine valves (not yet understood) caused a loss of load and a manual reactor trip was performed at 1108 [EDT]. Unit 3 is currently in Mode 3 [Hot Standby] and stable. Source Range Nuclear Instrument N-3-32 malfunctioned (loss of detector voltage). All other plant systems are working as designed."
Unit 3 is stable in Mode 3 [Hot Standby] at normal operating temperature and pressure. All control rods fully inserted. All other Nuclear Instrumentation is operable. Decay heat removal is via main feedwater and atmospheric steam dumps however, the condenser steam dumps are available but not preferred for Tave control. There is no known primary to secondary leakage. Unit 3 is in a normal shutdown electrical lineup. The cause of the turbine valves malfunction is not known at this time. There is no impact on Unit 4.
The licensee has notified the NRC Resident Inspector.
"This is a non-emergency event notification to the NRCOC [Nuclear Regulatory Commission Operations Center] in accordance with 10 CFR 50.72(b)(2)(iv)(B) for a valid actuation of the Reactor Protection System (RPS) (four hour notification).
"On 5/10/13 [at 1108 EDT] Unit 3 was stabilizing at 25% [power] during a controlled shutdown from an initial power level of 38% [power]. Prior to the planned insertion of the trip at 25% [power], a malfunction of the turbine valves (not yet understood) caused a loss of load and a manual reactor trip was performed at 1108 [EDT]. Unit 3 is currently in Mode 3 [Hot Standby] and stable. Source Range Nuclear Instrument N-3-32 malfunctioned (loss of detector voltage). All other plant systems are working as designed."
Unit 3 is stable in Mode 3 [Hot Standby] at normal operating temperature and pressure. All control rods fully inserted. All other Nuclear Instrumentation is operable. Decay heat removal is via main feedwater and atmospheric steam dumps however, the condenser steam dumps are available but not preferred for Tave control. There is no known primary to secondary leakage. Unit 3 is in a normal shutdown electrical lineup. The cause of the turbine valves malfunction is not known at this time. There is no impact on Unit 4.
The licensee has notified the NRC Resident Inspector.
Power Reactor
Event Number: 49022
Facility: MILLSTONE
Region: 1 State: CT
Unit: [] [2] []
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: VINCE WESSLING
HQ OPS Officer: JOHN SHOEMAKER
Region: 1 State: CT
Unit: [] [2] []
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: VINCE WESSLING
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 05/10/2013
Notification Time: 15:56 [ET]
Event Date: 05/10/2013
Event Time: 12:09 [EDT]
Last Update Date: 05/10/2013
Notification Time: 15:56 [ET]
Event Date: 05/10/2013
Event Time: 12:09 [EDT]
Last Update Date: 05/10/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
JAMES DWYER (R1DO)
JAMES DWYER (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
LOSS OF ASSESSMENT CAPABILITY DUE TO PLANNED TESTING OF RADIATION MONITORS
At 1209 EDT on 5/10/13, Stack Effluent radiation monitors RM8168 and RM8132 and Main Steam Line radiation monitors RM4299 A, B, and C were removed from service for planned testing. At 1458 EDT on 5/10/13, all radiation monitors were restored to service following completion of testing.
The licensee has notified the NRC Resident Inspector and the State and Local authorities.
At 1209 EDT on 5/10/13, Stack Effluent radiation monitors RM8168 and RM8132 and Main Steam Line radiation monitors RM4299 A, B, and C were removed from service for planned testing. At 1458 EDT on 5/10/13, all radiation monitors were restored to service following completion of testing.
The licensee has notified the NRC Resident Inspector and the State and Local authorities.
Power Reactor
Event Number: 49023
Facility: MONTICELLO
Region: 3 State: MN
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: MICHAEL STIDMON
HQ OPS Officer: STEVE SANDIN
Region: 3 State: MN
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: MICHAEL STIDMON
HQ OPS Officer: STEVE SANDIN
Notification Date: 05/10/2013
Notification Time: 15:56 [ET]
Event Date: 05/10/2013
Event Time: 09:20 [CDT]
Last Update Date: 05/10/2013
Notification Time: 15:56 [ET]
Event Date: 05/10/2013
Event Time: 09:20 [CDT]
Last Update Date: 05/10/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
10 CFR Section:
26.719 - FITNESS FOR DUTY
Person (Organization):
HIRONORI PETERSON (R3DO)
HIRONORI PETERSON (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Defueled | 0 | Defueled |
FITNESS-FOR-DUTY REPORT INVOLVING DISCOVERY OF ALCOHOL CONTAINER INSIDE THE PROTECTED AREA
"[The licensee] discovered a small bottle of alcohol within the Protected Area. The 50ml bottle was approximately 2/3 full. The seal ring had been broken. The clear liquid smells of alcohol as the label of the bottle indicates. The bottle was discovered beneath a deck structure to a temporary trailer that workers were demolishing.
"This event is reportable under 10CFR26.719 Fitness-For-Duty."
The license informed the NRC Resident Inspector.
"[The licensee] discovered a small bottle of alcohol within the Protected Area. The 50ml bottle was approximately 2/3 full. The seal ring had been broken. The clear liquid smells of alcohol as the label of the bottle indicates. The bottle was discovered beneath a deck structure to a temporary trailer that workers were demolishing.
"This event is reportable under 10CFR26.719 Fitness-For-Duty."
The license informed the NRC Resident Inspector.
Power Reactor
Event Number: 49024
Facility: LIMERICK
Region: 1 State: PA
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: PAUL MARVEL
HQ OPS Officer: STEVE SANDIN
Region: 1 State: PA
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: PAUL MARVEL
HQ OPS Officer: STEVE SANDIN
Notification Date: 05/10/2013
Notification Time: 18:08 [ET]
Event Date: 05/10/2013
Event Time: 09:05 [EDT]
Last Update Date: 05/10/2013
Notification Time: 18:08 [ET]
Event Date: 05/10/2013
Event Time: 09:05 [EDT]
Last Update Date: 05/10/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
10 CFR Section:
26.719 - FITNESS FOR DUTY
Person (Organization):
JAMES DWYER (R1DO)
JAMES DWYER (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
FITNESS-FOR-DUTY REPORT INVOLVING A NON-LICENSED SUPERVISOR TESTING POSITIVE FOR ALCOHOL
"A Non-licensed, Supervisory employee had a confirmed positive alcohol test during a random fitness-for-duty test. The employee's access to the Plant has been removed."
The licensee informed the NRC Resident Inspector.
"A Non-licensed, Supervisory employee had a confirmed positive alcohol test during a random fitness-for-duty test. The employee's access to the Plant has been removed."
The licensee informed the NRC Resident Inspector.
Agreement State
Event Number: 49305
Rep Org: NEW YORK CITY BUREAU OF RAD HEALTH
Licensee: THE CHILDREN'S HOSPITAL AT MONTEFIORE
Region: 1
City: BRONX State: NY
County:
License #:
Agreement: Y
Docket:
NRC Notified By: TOBIAS LICKERMAN
HQ OPS Officer: STEVE SANDIN
Licensee: THE CHILDREN'S HOSPITAL AT MONTEFIORE
Region: 1
City: BRONX State: NY
County:
License #:
Agreement: Y
Docket:
NRC Notified By: TOBIAS LICKERMAN
HQ OPS Officer: STEVE SANDIN
Notification Date: 08/23/2013
Notification Time: 14:05 [ET]
Event Date: 05/10/2013
Event Time: 00:00 [EDT]
Last Update Date: 08/23/2013
Notification Time: 14:05 [ET]
Event Date: 05/10/2013
Event Time: 00:00 [EDT]
Last Update Date: 08/23/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
WAYNE SCHMIDT (R1DO)
PAMELA HENDERSON (FSME)
FSME EVENTS RESOURCE (EMAI)
WAYNE SCHMIDT (R1DO)
PAMELA HENDERSON (FSME)
FSME EVENTS RESOURCE (EMAI)
AGREEMENT STATE REPORT - POTENTIAL OVEREXPOSURE TO FAMILY MEMBER
A family member may have received an exposure of 5,925 mrem while providing home care for the patient undergoing I-131 therapy administered on March 22, 2013. The patient was hospitalized from March 22 to March 29, 2013 and then discharged with at-home precautions.
During the patient's hospitalization visitors including family members were provided radiation badges to monitor exposure. The badges were subsequently processed by Landauer on May 5, 2013 which identified that a family member received 5,925 mrem effective dose equivalent during this period of hospitalization. The subject badge was reread on May 6, 2013 which confirmed the initial reading. The Children's Hospital was notified on May 10, 2013 of the results. A survey of the patient's room found little contamination.
Children's Hospital conducted an extensive investigation but could not definitively identify the cause for the high exposure level.
A family member may have received an exposure of 5,925 mrem while providing home care for the patient undergoing I-131 therapy administered on March 22, 2013. The patient was hospitalized from March 22 to March 29, 2013 and then discharged with at-home precautions.
During the patient's hospitalization visitors including family members were provided radiation badges to monitor exposure. The badges were subsequently processed by Landauer on May 5, 2013 which identified that a family member received 5,925 mrem effective dose equivalent during this period of hospitalization. The subject badge was reread on May 6, 2013 which confirmed the initial reading. The Children's Hospital was notified on May 10, 2013 of the results. A survey of the patient's room found little contamination.
Children's Hospital conducted an extensive investigation but could not definitively identify the cause for the high exposure level.